Nuclear engineering plant and closure apparatus for its containment

ABSTRACT

A nuclear engineering plant has a containment, whose interior chamber is subdivided by a wall into a systems chamber and an operating chamber which is accessible during normal operation. The containment ensures a particularly high operational reliability, in particular also in incident situations, in which hydrogen is released in the systems chamber. For this purpose, a number of overflow openings are provided in the partition wall, the respective overflow opening is closed by a closure element of a closure apparatus which opens automatically when a trigger condition associated with the respective overflow opening is reached. Closure apparatuses are provided which open both as a function of pressure and independently of pressure. The closure apparatus furthermore has a closure element containing a bursting film or a bursting diaphragm. The closure apparatus is configured such that it frees the overflow opening automatically when a predetermined environment-side trigger temperature is reached.

CROSS-REFERENCE TO RELATED APPLICATION

This is a continuation, under 35 U.S.C. §120, of copending internationalapplication PCT/EP2007/000572, filed Jan. 24, 2007, which designated theUnited States; this application also claims the priority, under 35U.S.C. §119, of German patent application DE 10 2006 010 826.4, filedMar. 7, 2006; the prior applications are herewith incorporated byreference in their entirety.

BACKGROUND OF THE INVENTION Field of the Invention

The invention relates to a nuclear engineering plant, in particular to apressurized-water reactor, with a containment. The interior of which isdivided by a gas-tight intermediate wall into a plant space containing areactor pressure vessel and a primary cooling circuit and into anoperating space which is walkable during normal operation. In addition,a plurality of overflow openings are formed in the intermediate wall.The invention further relates to a closure apparatus for an overflowopening disposed in the intermediate wall.

Within the context of the safety-related configuration of a nuclearpower plant, the reactor pressure vessel enclosing the reactor core isusually arranged in a containment. The containment contains a largenumber of redundant and diversified safety apparatuses which ensurereliable cooling of the reactor core in cases of disruptions to thenormal operation of the nuclear power plant, in particular if thereactor core experiences a loss in coolant. The containment additionallyensures, as a gas-tight mantle which is often kept at a negativepressure with respect to the surrounding area, that even in case of anincident no radioactivity can leak into the surrounding area. The termcontainment also encompasses the atmosphere it encloses.

Most of the plants built to date have so-called single-spacecontainments without clear separation of the internal volumes which arenot walkable during normal operation. This makes control and maintenancework in the containment difficult. If the interior of the containment isto be accessed, the reactor usually needs to be shutdown beforehand in atimely manner and the containment atmosphere be decontaminated, whichcan entail relatively long downtimes.

In order to circumvent such difficulties, so-called two-spacecontainments have already been proposed, in which the interior of thecontainment is divided by a gas-tight intermediate wall, generally aconcrete intermediate wall, into a plant space containing the reactorpressure vessel and the primary cooling circuit and into an operatingspace which is screened off therefrom in terms of radiation andventilation and can also be accessed during operation. In this concept,during normal operation the plant space with the active and high energyprimary circuit components which are contaminated to a greater degree istherefore completely separated and screened off from the remainingcontainment areas which are walkable and thus accessible for maintenancepurposes, the so-called operating space.

In the case of incidents and especially accidents with increased coretemperatures, which can be caused for example by a leak in the primarycooling circuit, a massive release of steam and explosive gases,primarily hydrogen, into the internal separated-off space areas of thecontainment can occur under certain circumstances. Especially in thecase of a two-space containment of the type described above, arelatively rapid rise in pressure and a strong concentration ofignitable gases can occur within the comparatively small volume of theplant space. Even with smaller leak cross sections which lead only to acomparatively slow build-up in pressure in the plant space, criticalconcentrations of ignitable gases or explosive gas mixtures can arise inlocalized fashion due to the limited expansion volume.

In such cases of incidents or accidents, the aim is therefore for aneffective distribution of the incident atmosphere in the entirecontainment volume which restricts the local and global maximumconcentrations of ignitable gases. To this end, the intermediate wallcontains, between the plant space and the operating space, overflowopenings which have hitherto been closed primarily with bursting screensand which open when the bursting pressure is reached. Since certainfluctuations in the bursting tolerance are unavoidable in theconfiguration and manufacture of the bursting elements, the solutiondescribed has the disadvantage, however, that, especially in the morelikely incident situations with smaller leaks and slower build-up inpressure, typically only that bursting element with the lowestindividual bursting pressure opens. The pressure equalization thusinduced generally prevents the opening of the other bursting elements.As a result of the only partial space opening, the convectivedistribution of the gases which are capable of detonating is severelyrestricted, with the result that the risk of explosion must be reducedby way of increased use of inertization apparatuses and recombiners orthe like. Such measures are generally comparatively complex andexpensive and cannot be regarded as optimum in view of the level ofsafety which can be achieved.

Other safety concepts which have to date been conceived and, in part,realized envisage, additionally or alternatively to the burstingscreens, hand-operated flaps which can be operated or actuated by way ofcable pulls or else electromotorically by the operators stationedoutside the containment in order to release the overflow cross sectionsin case of emergency. However, hand-operated emergency devices haveproven too slow and too unreliable in many incident scenarios,especially in the case of those which involve a very early hydrogenrelease, and are also severely limited in terms of number and openingcross section due to the high outlay necessary. In general, anyerroneous operations which are based on human failure or on situationalmisjudgement should be precluded from happening in advance in asafety-critical plant such as a nuclear power plant. Alternativesolutions with motor-driven closure flaps are problematic due to theirdependence on an intact energy supply. Furthermore, these motor-drivenclosure flaps are not effective in the case of large fracture crosssections of high energy pipelines due to the delayed opening to relievepressure and the significant space requirement (drive, transmission,etc.) results in that no relevant installation spaces forpressure-relief elements are available. Detailed H₂ distribution andpressure build-up analyses carried out in accident situations involvingmassive H₂ releases utilizing the above devices generally confirm thisproblem.

SUMMARY OF THE INVENTION

It is accordingly an object of the invention to provide a nuclearengineering plant and a closure apparatus for its containment whichovercome the above-mentioned disadvantages of the prior art devices ofthis general type, which ensures particularly high operational safety,in particular also in incident situations with relevant hydrogen releasein the core area or primary cooling circuit, while keeping complexity interms of manufacture and operation low. The invention furthermorespecifies a closure apparatus, which is particularly suitable for use insuch a plant, for a pressure relief and overflow opening disposed in theintermediate wall between plant space and operating space.

With the foregoing and other objects in view there is provided, inaccordance with the invention, a nuclear engineering plant. The plantcontains a containment including an interior and a gas-tightintermediate wall dividing the interior into a plant space having areactor pressure vessel and a primary cooling circuit and into anoperating space being walkable during normal operation. The gas-tightintermediate wall has a plurality of overflow openings formed therein.The containment further has closure apparatuses with closure elementseach closing a respective one of the overflow openings. The closureelements open automatically when a trigger condition associated with therespective overflow opening has been reached. The closure apparatusesopens in dependence on a pressure and opens independently of thepressure.

The object is achieved according to the invention with respect to thenuclear engineering plant by virtue of the fact that the respectiverelief and overflow opening is closed by a closure element of a closureapparatus which opens automatically when a trigger condition associatedwith the respective overflow opening has been reached, wherein closureapparatuses which open as a function of pressure and which openindependently of pressure are provided.

The invention proceeds from the consideration that in a nuclearengineering plant of the type mentioned in the introduction, even in thecase of an incident with possibly massive release of steam and flammableor explosive gases, the local and global maximum concentrations of thesegases should be kept to a minimum already for type and design reasons.Mixtures which are capable of detonating and could endanger theintegrity of the containment should not even be allowed to occur in thefirst place. In case of an incident occurring inside the plant space,rapid opening of the space should therefore follow for the purposes ofthe effective distribution of the incident atmosphere and limitation ofthe gas concentrations in the entire containment volume. The closureapparatuses, which are arranged in the overflow openings of theintermediate wall and which, in the closed state, ensure the spaceseparation and the separation of plant space and operating space interms of ventilation and radiation protection during normal operation,should additionally be constructed in accordance with the designprinciples diversity, passivity, redundancy and failure safety suchthat, if an incident occurs, an automatic and self-supporting opening orrelease of the overflow cross sections preferably without the need foroutside energy follows.

For a particularly effective distribution of the gases which arereleased due to the incident and their mixing with the entire remainingcontainment atmosphere and for effective pressure relief in the plantspaces in the case of large pipeline fractures, not merely individualbut a number of, ideally many or even all of the closure elements shouldrelease the flow passages they block during normal operation at the sametime or at least nearly at the same time. This should also apply inparticular in the case of comparatively small leaks in the primarycircuit and the associated slow build-up of pressure. To this end,according to the present concept, provision is made first for in eachcase one incident-related trigger condition to be associated with theclosure apparatuses which are independent of one another, with thetrigger condition taking into consideration the specific ambientconditions, operational parameters and influence factors at therespective site of use, i.e. at the site of the respective overflowopening. Second, in addition to a purely pressure-dependent triggermechanism which can be realized for example simply by way of aconventional bursting film or the like, or as an alternative thereto, atleast for some of the closure apparatuses at least one further triggerprinciple which is not dependent on pressure is provided. Such adiversified design of the closure apparatuses or of the associatedtrigger apparatuses and the selection, which is matched to therespective overflow opening, of the trigger parameters, the thresholdvalues, the sensitivities etc. result in an early and nearlysimultaneous response to even comparatively harmless incident situationsin not just a single one, but in a large number of decentrally triggeredclosure apparatuses which are independent of one another.

In order to achieve the intended diversity, the nuclear engineeringplant can advantageously have at least two types of closure apparatuses,where the operating principles thereof which form the basis of thetrigger procedure and/or the operation procedure differ. Alternativelyor additionally thereto, however, at least one closure apparatus mayalso be provided, in which a plurality of trigger apparatuses which arebased on differing operating principles are combined.

A nuclear engineering plant, where closure apparatuses which open as afunction of the temperature are provided in addition to the closureapparatuses which open as a function of pressure, is particularlyadvantageous. This is because, in the case of a slow build-up ofpressure in the plant space, generally only one or few of thepressure-sensitive closure apparatuses or bursting elements open whenthe individual trigger pressure or bursting pressure is reached, whichin itself could entail an only inadequate space opening and mixing ofthe containment atmosphere. Since during an incident usually also thetemperature in the plant space increases at the same time, for exampledue to hot steam escaping from a leak in the primary circuit, furtheroverflow cross sections are released by the temperature-sensitiveclosure apparatuses which result in an effective distribution of theincident atmosphere.

Advantageously, at least one closure apparatus is configured such thatit opens automatically as soon as the atmosphere pressure in the plantspace exceeds a predetermined trigger pressure. Rather than a triggercondition relating to an absolute value of the pressure, it is alsopossible for a relative criterion to be used such that at least oneclosure apparatus opens automatically as soon as the pressure differencebetween the plant space and the operating space exceeds a predeterminedtrigger value. The trigger value is preferably approximately 20 mbar to300 mbar.

Furthermore, at least one closure apparatus is configured such that itopens automatically as soon as the local atmosphere temperature at ameasurement location in the plant space exceeds a predetermined triggertemperature. Advantageously, the associated temperature-dependenttrigger or unlocking apparatus is integrated in the closure apparatus,i.e. the measurement location is situated directly where the closureapparatus is mounted or at or in the overflow opening. Alternatively oradditionally to this, it is also possible, however, for at least oneclosure apparatus to be provided, in which a closure element is coupled,via a remote-controlled apparatus, to a temperature-dependent triggerapparatus which is positioned near the ceiling of the plant space. It isexpedient here if a closure element arranged in the lower region of theplant space can be actuated or unlocked by way of a fusible solderdevice arranged at a higher level or the like, with the result that thehigher temperatures occurring in the upper regions in case of atemperature stratification (temperature layering) are utilized for theunambiguous triggering and reliable opening of the lower overflowdevices, too.

The trigger temperature is expediently matched to the room temperaturein the plant space which is provided for normal operation and isadvantageously kept below 60° C. by an air recirculation and coolingsystem. It is preferably selected from the interval from approximately65° C. to 90° C. In a particularly expedient refinement, the triggertemperatures of the closure apparatuses which open as a function oftemperature are selected in a staggered manner or such that theyincrease as the installation height of the apparatuses increases, e.g.from 65° C. to 90° C., which takes the temperature stratification in theplant space into account. Thus, a rapid and approximately simultaneousopening of all the closure apparatuses is favored in this case, too.

In an advantageous development, at least one closure apparatus isconfigured such that it opens automatically as soon as the concentrationof a gas which is flammable or capable of exploding and is present inthe atmosphere of the plant space, in particular the concentration ofhydrogen, exceeds a predetermined trigger concentration. Therefore,another diversification of the trigger criteria in addition to apressure-sensitive and temperature-sensitive triggering is achieved bythe concentration of the ignitable gases being monitored, whereinexceeding a predetermined limit value leads to the automatic opening ofthe closure apparatuses which close during normal operation the overflowcross sections. Advantageously, the trigger concentration isapproximately 1 to 4 percent by volume of H₂.

In a particularly advantageous refinement, such aconcentration-sensitive triggering can be achieved by a catalyticelement, which releases heat in the presence of explosive or ignitablegases, or a H₂ recombiner being arranged near a closure apparatus whichopens as a function of temperature or near a temperature-sensitivetrigger apparatus which is associated therewith such that the heatreleased thereby triggers the opening of the closure apparatus when athreshold value is exceeded. By way of example, the respectiverecombiner is arranged just underneath a fusible solder opening devicewhich initiates the opening of the closure element, with the result thatthe increased operating temperature in the recombiner in case H₂ ispresent causes reliable opening of the overflow cross section in adiversified manner—i.e. even in case of otherwise low room temperaturesand independently of any release of steam. Instead of a recombiner, orin addition thereto, a catalytic element on the basis of a metalliccarrier with washcoat coating and the catalytically active materialsplatinum and/or palladium can, for example, also be provided. Ifhydrogen is present, the exothermic heat of reaction ensures even at aconcentration of from 1 to 4 percent by volume reliable triggering ofthe temperature-sensitive closure apparatus, even independently of theother room temperature.

Furthermore, a first subset of the overflow openings, which are in eachcase provided with one of the closure apparatuses, is advantageouslyarranged in the lower third, in particular near the floor of the plantspace, and a second subset is advantageously arranged in the higherregions, in particular in the sections of the intermediate wall whichform the ceiling of the plant space. The difference in height betweenthe high and low overflow openings is here preferably more than 5 m, inparticular more than 20 m, in order to effectively drive in a passivemanner the convection rollers by way of the difference in density of theatmosphere columns between the plant and the operating spaces. Here,there is expediently a number of recombiners mounted on the inside wallof the plant space between the lower and the higher overflow openings.Due to the reduced density resulting in the case of an incident from thefailure of the space cooling or due to the release of steam, the chimneyeffect in the plant spaces which is possibly even increased by the heatof reaction of the catalytic recombiners is used to drive large-areaconvection rollers in the containment. In this manner, an increase ofthe overflow speeds to 0.5 m/s to 2 m/s or more is achieved. The mannerin which the recombiners are expediently arranged here is selected suchthat an increased release of heat of reaction in the so-called chimneyregion of the plant spaces, i.e. in the upper regions of the steamgenerator towers and above the low overflow openings is achieved. Inthis manner, the recombiners are impacted by flow with increased entryspeed after the space opening, which favors a particularly effectivehydrogen reduction. Particularly preferably, the recombiners arearranged inside the plant space such that the H₂ reduction power in theplant spaces is more than 20% of the overall H₂ reduction power of forexample more than 50 kg/h.

Large pressure-relief areas become possible through the combination ofthese relief and overflow elements which can now all largely open as afunction of pressure. Preferably, the area covered overall by theclosure elements is approximately 0.1 to 0.5 times the horizontalcross-sectional area of the plant space. This also leads to a seriouslimitation in the difference pressure loading in the plant spaces evenin the case of serious pipeline fractures, with the result that a planarsteel beam holding and sealing construction is made possible even in thecase of only limited load reduction (due to the technically possiblesection moduli). In this manner, the pressure loads occurring in thecase of serious pipeline fractures and large leaks are limited to lessthan 0.5 times, in particular to less than 0.2 times, the designpressure for the containment. In order to ensure a particularlyeffective convection even in the case of small leaks, the total area ofthe overflow openings per steam generator tower is moreoveradvantageously more than 1 m², in particular more than 5 m².

Advantageously, the nuclear engineering plant has a cooling apparatus,in particular in the form of an air recirculation and cooling system,for cooling the air in the plant space, wherein the cooling power of thecooling apparatus is preferably such that the room temperature in theplant space can be reduced during normal operation permanently to lessthan 60° C. The cooling minimizes in particular the chimney effect,which is established during normal operation, in the plant space withrespect to the operating space and thus the pressure differenceinfluencing the seals of the closure elements. Furthermore, the nuclearengineering plant contains a suction apparatus for the air which is inthe plant space and a purifying apparatus, which is connected upstreamor downstream on the flow side of the suction apparatus, for purifyingand decontaminating the sucked-off air. During normal operation, aslight negative pressure of approximately 10 Pascal or more with respectto the operating space is thus produced in the plant space due to theair being sucked off from the plant space, wherein the pressuredifference must not exceed the trigger value which leads to bursting ofthe bursting elements or else to pressure-dependent opening of theclosure apparatuses. The sucked-off space air is purified as far aspossible in aerosol and iodine filters before it is given off to thesurrounding area.

A particularly expedient closure apparatus for one of the overflowopenings of the nuclear engineering plant advantageously has a closureelement containing a bursting film or a bursting screen, wherein theclosure apparatus is configured such that it automatically releases theflow cross section when a predetermined trigger temperature on the sideof the surrounding area is reached. In other words, the two functions“pressure-dependent opening” and “temperature-dependent opening” arecombined in a single closure apparatus, wherein the closure apparatuswhich is configured as a passive element opens automatically,autonomously, without delay and preferably without the need for outsideenergy (as per the failsafe principle) when one of the two triggerconditions (trigger pressure or trigger temperature) is reached, andreleases the overflow cross section. This minimizes the number ofclosure apparatuses necessary for a diversified design of the openingmechanisms and enables the accommodation of correspondingly largeopening areas of closure elements within planar ceiling constructions.Such a construction furthermore limits the difference pressure acting onthe respective apparatus during maximum pressure increase, so that aparticularly cost-effective construction of the respective openingelement and of the structures of the plant spaces loaded by thedifference pressure becomes possible. Here, the pressure-dependentopening in proven fashion by way of a bursting film or bursting screen,which forms the actual closure element or is integrated in the closureelement, is realized.

Advantageously, the respective closure apparatus contains an actuatingapparatus which acts, in the case of a temperature-dependent triggering,directly on the bursting screen or on the bursting film and results inthe destruction or tearing of the latter. This is preferably aspring-driven actuating apparatus. The closure apparatus furthermorepreferably contains a locking apparatus which blocks the actuatingapparatus before the trigger temperature is reached or compensates forit in terms of its effect. By way of example, a tension spring, which ispre-tensioned but blocked during normal operation by a fusible solderdevice, can be fixed directly and approximately centrally on thebursting film such that the tension spring is released when the meltingtemperature is reached, with the tension spring in that case tearing thebursting film following its release.

According to an advantageous alternative embodiment, the bursting screenor the bursting film can also be mounted, or clamped in, on a frameelement which is mounted such that it can rotate or pivot on the wall.The frame element can be fixed in the closed position by a lockingelement and the locking element is configured, or coupled to atemperature-dependent trigger apparatus, such that it is unlocked whenthe trigger temperature is reached. By way of example, the burstingelement can be held in a frame element which is pressed against a planarsupporting and sealing construction via a fusible solder apparatus. Whenthe melting temperature is reached, the entire frame element is releasedand opens due to gravity and/or the spring force. Iftemperature-dependent triggering has not yet taken place, alternativelythe bursting film or the bursting screen in the closure element openswhen the bursting pressure is reached.

The fusible solder apparatuses are expediently concentrated on a holdingelement or a few holding elements on the frame and are provided withtensioning elements. On account of the construction, thecontact-pressure force is distributed over the sealing elements suchthat a sufficient tightness is achieved and a simple functionalexamination or a simple exchange is made possible.

In another advantageous variant, the triggering and opening of theclosure element is effected using a trigger apparatus which is disposedremote from the closure element and acts in a trigger event via amechanical or pneumatic/hydraulic remote-controlled apparatus on theclosure element or the associated locking element. For example, atrigger apparatus containing a fusible solder or a fusible bead can bemounted in the higher regions of the plant space, wherein the triggeringis transmitted via a cable pull or a tensioned spring element or thelike to a lower closure element. In an alternative system, in a triggerevent, a pipeline which is connected to a pressure accumulator or to oneor more hydraulic reservoirs and is closed during normal operation by afusible bead or a fusible solder is released, so that as a consequenceof the starting application of pressure, a closure element which isarranged at a distance is unlocked or opened.

The closure element is preferably configured and mounted on the wallsuch that the process of opening is driven or assisted by the inherentweight of the closure element. Suitable for this purpose is inparticular horizontal fitting in the ceiling, wherein for example aclosure element, which is in the form of a type of closure flap, ismounted with one or more hinges in the ceiling wall or anothersupporting construction and flaps downward to open during the process ofopening.

In particular if the closure element is fitted vertically, it isexpedient to provide a spring element or a compression leg which assistsin the process of opening.

Alternatively or in addition thereto, overflow cross sections can alsobe opened by way of motor-actuated overflow flaps. These flaps are inthis case preferably kept permanently closed in a motor-driven way andopen due to spring force and/or their inherent weight. Here, opening canbe triggered via a suitable measurement and control apparatus when apredetermined absolute or difference pressure or a trigger temperatureis reached. If there is no voltage at the drive motor or the associatedprocess control technology or when the trigger criterion (e.g. pressure,temperature or gas concentration) is reached, the closure element thenopens reliably and without the need for outside energy as per thefailsafe principle. In order to limit the difference pressure loading,closure elements of this type can also be fitted with bursting films.

The use of these overflow flaps, which are motor-actuated or held closedusing motor force and can be especially in the form of louver flaps orof rotary pendulum flaps with spring return actuator, is expedientparticularly in the low, temporarily cold inflow region of the plantspace or of the intermediate wall delimiting it from the operatingspace, especially in combination with the temperature-sensitive andpressure-sensitive, large-area closure apparatuses, described above, inthe high overflow regions. In order to ensure sufficient screening inthe inflow opening region of the plant space, screening walls areprovided upstream of the respective inflow device. The screening devicescan also be arranged such that they are aligned radially in the lowerthird of the intermediate wall. The free convection cross section shouldbe at least twice that of the inflow cross section.

The respective bursting film or bursting screen of the closure elementis advantageously configured such that it tears or breaks, when apredetermined trigger pressure is applied to it, in the direction ofboth sides depending on the direction of attack of the pressure force.Thus, an opening of the overflow cross sections is also triggered in thecase of an external positive pressure in the operating space, caused forexample by a fracture of a secondary-side live-steam line. Moreover, thebursting elements are expediently configured such that, when radiationforces impact, no relevant fractured pieces can occur which couldpossibly cause secondary damage. Therefore, the bursting films areexpediently configured such that they break in the one direction bytearing of the provided bursting material webs and in the oppositedirection primarily by kinking. For sealing purposes, easily tearablesealing films with a thickness of less than 0.05 mm can additionally beused. In the event of negative or positive pressures of 20 mbar to 300mbar, the bursting films thus expediently open in both directions.

The advantages attained by the invention are in particular that firstthe active and high energy plant components in a nuclear engineeringplant, in particular in a pressurized-water reactor, are hermeticallyscreened during normal operation against the surrounding operatingspaces which thus remain walkable for any occurring control andmaintenance work, and second, in incident and accident situations, withthe danger of the release of ignitable gases, rapid, reliable andlarge-area space opening using passive, failure-safe elements on thebasis of diversified operating principles is effected. The convectivedistribution of the released gases, optimized by a manner of arrangingthe overflow cross sections such that they are staggered in height,particularly reliably and simply effects a limitation of the maximumlocal concentrations, so that mixtures which are capable of detonatingand could endanger the integrity of the containment are reliablyavoided. Thus, the invention serves to increase the safety reserves in anuclear reactor with simultaneous significant reduction in complexityand costs.

Other features which are considered as characteristic for the inventionare set forth in the appended claims.

Although the invention is illustrated and described herein as embodiedin a nuclear engineering plant and a closure apparatus for itscontainment, it is nevertheless not intended to be limited to thedetails shown, since various modifications and structural changes may bemade therein without departing from the spirit of the invention andwithin the scope and range of equivalents of the claims.

The construction and method of operation of the invention, however,together with additional objects and advantages thereof will be bestunderstood from the following description of specific embodiments whenread in connection with the accompanying drawings.

BRIEF DESCRIPTION OF THE SEVERAL VIEWS OF THE DRAWING

FIG. 1 is a diagrammatic, longitudinal sectional view of a containmentfor a nuclear engineering plant according to the invention;

FIG. 2 is a diagrammatic, sectional view of a closure apparatus, whichopens automatically in an event of a plant incident, for an overflowopening of the nuclear engineering plant shown in FIG. 1;

FIG. 3 is a diagrammatic, sectional view of two closure apparatuses ofdifferent types in a combined arrangement;

FIG. 4 is an illustration of a pressure-sensitive and atemperature-sensitive closure apparatus installed in a wall of thenuclear engineering plant as shown in FIG. 1, illustrated in an openstate after a temperature-related triggering caused using aremote-controlled apparatus;

FIG. 5 is a diagrammatic, sectional view of a remote-controlledapparatus of the closure apparatus as shown in FIG. 4 before a start ofa trigger event; and

FIG. 6 is an illustration of the closure apparatus as shown in FIG. 4after a pressure-related triggering.

DETAILED DESCRIPTION OF THE INVENTION

Components having the same design or the same function are indicated bythe same reference numbers in each of the figures. Referring now to thefigures of the drawing in detail and first, particularly, to FIG. 1thereof, there is shown in a longitudinal section a containment 2, whichextends largely symmetrically with respect to a longitudinal axis 1, ofa nuclear engineering plant 4 with a pressurized-water reactor. Thecontainment 2 has inside nuclear components for generating hot andpressurized water steam, in particular a reactor pressure vessel 8 and aprimary cooling circuit 10 connected to the former with a number ofsteam generators 12, and other system components. The shell forming thecontainment 2 also prevents activity transfers to the surrounding areain the case of a comparatively serious operational incident by closingin and keeping back coolant from escaping for example from a leak in theprimary cooling circuit 10. Usually, the shell of the containment 2 ismade of steel and is additionally surrounded by a non-illustratedconcrete cladding.

The nuclear engineering plant 4 is configured for a particularly highoperational reliability, wherein at the same time an extremelyeconomical mode of operation is made possible. For this purpose, aninterior 14 of the containment 2 is divided by a gas-tight intermediatewall 16 into a plant space 18 containing the reactor pressure vessel 8and the primary cooling circuit 10, i.e. containing the active and highenergy components, and into an operating space 20 which contains theother system components which are only comparatively weakly loaded withradioactivity. The plant space 18 and the operational space 20 arepossibly in turn divided into further subspaces, but this is of nofundamental importance for the safety-related concept which will beexplained below and for the associated design principles. Theintermediate wall 16 is generally configured in a comparatively massivesteel concrete construction, so that in addition to the ventilation-sideseparation of operational space 20 and plant space 18, a notinsignificant screening effect against the radiation which is releasedinside the plant space 18 is also still realized. Thus, the operationalspace 20 remains walkable even during the operation of the nuclearengineering plant 4, and is thus easily accessible for any necessarycontrol and maintenance work. The operation of the reactor generallyonly needs to be interrupted for maintenance work on the high energynuclear components which are contaminated to a greater degree and aresituated within the plant space 18.

Within the context of an operational incident, caused or accompanied forexample by a leak in the primary cooling circuit 10, relevant amounts ofignitable and possibly explosive gases, in particular hydrogen, couldalso be released into the plant space 18 in addition to a release of hotsteam. Since the volume of the plant space 18 is kept comparativelysmall, after a certain time critical concentrations would under certaincircumstances be exceeded, at which an increased risk of explosion wouldhave to be expected. In order to reliably preclude such critical statesin advance, arranged in the intermediate wall 16 separating the plantspace 18 from the operational space 20 is a number of overflow openings22 a, 22 b, 22 c which are closed in a gas-tight manner during normaloperation by way of respectively assigned closure elements 24, but whichrelease in the event of an incident or of a disaster state in the plantspace 18 the respective overflow cross section early and, for reasons ofan effective distribution of the incident atmosphere, in the entirecontainment 2. The respective closure element 24 is a constituent partof a passive closure apparatus 26 which effects, when a triggercondition which is considered to be an incident indicator is reached orexceeded, the opening of the overflow cross section automatically andwithout the need for outside energy.

During normal operation, a slight negative pressure with respect to theoperational space 20 is generated in the plant space 18 by sucking offthe atmosphere therein; the pressure difference here is approximately 10Pa to at most 1,000 Pa. For reasons of sucking off the air, a suctionapparatus denoted 28 in FIG. 1 is provided, which contains a suctionline 30, which is guided through the intermediate wall 16 and throughthe containment 2 from the plant space 18 to the outside, and a suctionpump 32 connected thereto. Before it escapes into the surrounding area,the air sucked off from the plant space 18 is purified anddecontaminated with the aid of a multistage purifying apparatus 34 whichis connected into the suction line 30 and contains a number of aerosoland iodine filters. Furthermore, the heat arising in the plant space 18is continuously removed by an air recirculation and cooling system (notillustrated further here) such that the room temperature in the plantspace 18 is, during normal operation, below a maximum value ofapproximately 60° C.

In the event of an incident which is due to a leak in the primarycooling circuit 10, the release of hot steam and gases produces anincrease in pressure and also an increase in temperature inside theplant space 18, wherein furthermore the hydrogen content in the air orthe concentration of other ignitable gases can rise. The pressure in theplant space 18 or the difference pressure with respect to theoperational space 20 and the atmospheric temperature are thereforeparticularly relevant and suitable parameters for monitoring the nuclearengineering plant 4 for the occurrence of incidents. The closureapparatuses 26 are configured and constructed such that theyautomatically respond and effect the opening of the overflow crosssections as soon as one or more of the operational parameters (pressure,temperature, H₂ concentration) exceeds a threshold value which is to beconsidered to be an incident indicator. Due to the diversifiedconfiguration of the closure apparatuses 26 with respect to theirtrigger and actuation mechanisms, an extremely reliable andcomparatively large-area space opening is achieved here even in the caseof the more likely incident situations with comparatively slow build-upof pressure.

Moreover, the specific manner in which the overflow openings 22 a, 22 b,22 c are arranged in the intermediate wall 16 separating the plant space18 from the operating space 20 ensures in the trigger event optimizedflow conditions which promote rapid and uniform distribution of thereleased ignitable gases in the entire containment volume. For one, anumber of comparatively low overflow openings 22 a withpressure-sensitive and temperature-sensitive closure apparatuses 26which open automatically in the trigger event are provided in verticalinstallation in the lower third of the plant space 18. Secondly, aplurality of such closure apparatuses are arranged in the overflowopenings 22 b of a ceiling 36 above the steam generator 12 (horizontalinstallation) and in the process form, as it were, an overflow ceiling.In order to adequately take into account the possible temperaturestratification in the plant space 18, the trigger temperatures of thehigh closure apparatuses 26 with approximately 90° C. are selected to behigher than those of the low closure apparatuses 26 at approximately 65°C. Furthermore, in the area near the floor, motor-actuated overflowflaps 38 are installed in the overflow openings 22 c located there,which are normally kept closed by an electromotor 40 and which in thetrigger event, i.e. if the electromotor 40 is switched off or withoutvoltage, open by way of spring force or gravity as per the failsafeprinciple.

As already explained, the diversification of the trigger mechanismsensures that in the event of an incident in the core region of thereactor or in the primary cooling circuit 10, the predominant or atleast a relevant number of closure apparatuses 26 or closure elements 24open. This results in the flow course illustrated by flow arrows 42 inthe right-hand part in FIG. 1, where the hot gases and steam escape thehigh overflow openings 22 b in the ceiling 36 of the plant space 18upward, cool off on the above ceiling of the containment 2 andsubsequently drop downward in the ring-shaped intermediate space 44between the intermediate wall 16 and the inside wall of the containment2, in order to finally flow in again through the opened overflow crosssections 22 a, 22 c into the plant space 18. Circulating the flow causesan extremely effective mixing of the previously separated “internal” and“external” containment atmosphere, which reliably limits the maximumconcentrations of gases or gas mixtures which are capable of detonatingand could endanger the integrity or stability of the containment 2.

The flow cross section in the intermediate space 44 between theintermediate wall 16 and the inside wall of the containment 2 isnarrowed by screening elements 114, which results in a particularlyadvantageous flow guidance. In the exemplary embodiment, the screeningelements 114 form altogether a type of ring stop which is installed inthe intermediate wall 16, approximately at a third of the height of theplant space 18. The remaining free convection cross section or inflowcross section 115 is about three times as large as that of the overflowopenings 22 a, 22 c which are located underneath the screening elements114 just as the inflow cross section.

Moreover, a plurality of catalytic recombiners 46 are used to reduce thereleased hydrogen and are disposed preferably on the inside wall of theplant space 18, in particular around the steam generators 12, such thatthey are impacted by the flow of the rising atmosphere at comparativelyhigh entry speed when the overflow ceiling 36 is opened. The reductionin hydrogen is particularly effective in that case. Due to the heat ofreaction, the overflow speeds in the high, ceiling-side overflow crosssections are increased to up to 2 m/s or more. Finally, at least some ofthe recombiners 46 are disposed near the temperature-sensitive closureapparatuses 26 such that the heat of reaction thereby produced with theoccurrence of H₂ results in the trigger temperature being exceeded, i.e.in the opening of the respective overflow opening, even if the roomtemperature is otherwise rather relatively low. Due to this multiple useof the recombiners 46 used in the nuclear engineering plant 4 it ispossible therefore to implement in a simple and cost-effective manner anadditional trigger mechanism for the closure apparatuses 26 which isdependent on the hydrogen concentration.

FIG. 2 shows by way of example the closure apparatus 26 which combinesthe two functions of pressure-dependent opening andtemperature-dependent opening. In the embodiment shown here, the closureapparatus 26 is particularly suitable for horizontal installation in theceiling 36 or the ceiling wall of the plant space 18 of the nuclearengineering plant 4; however, modifications with inclined or verticalinstallation positions, e.g. in a side wall, are also conceivable.

The closure apparatus 26 contains the closure element 24 which isprovided for covering an overflow opening 22 and has a bursting film 50which is clamped in a first frame element 48. The first frame element 48has, in plan view from the direction denoted by directional arrow 52, arectangular basic area. The frame element 48 itself is made of hollowbeams which have a square cross section or with the use of other, e.g.open, steel profiles (L, U profile combinations). The first frameelement 48 supporting the bursting film 50 is fixed using hinges 56 suchthat it can pivot to a second frame element 58 such that the completeclosure element 24 can be opened in the case of need in the manner of awing or a door or a pull-open window with respect to the second frameelement 58 which is fixedly connected to a sealing and holdingconstruction 60 and serves at the same time as a bearing and stop forthe first frame element 48. The sealing and holding construction 60 forits part is fixedly anchored in a non-illustrated concrete ceiling orintermediate wall of the nuclear engineering plant. The two frameelements 48, 58 are arranged underneath the holding construction 60 sothat the closure element 24 can freely flap downward to open in atrigger event.

During normal operation of the nuclear engineering plant 4, the closureelement 24 is kept closed in a gas-tight manner, that is to say it is inthe uppermost of the three positions which are illustrated in FIG. 2 andindicate the movement profile during opening.

The two frame elements 48, 58 then congruently overlap each other,wherein a high gas-tightness is achieved by way of providing sufficientcontact pressure and, if appropriate, by way of a sealing device (notillustrated further here). This closed state is maintained during normaloperation with the aid of a locking apparatus 64 containing fusiblesolder 62, which locking apparatus 64 is arranged on the two frameelements 48, 58 opposite that side of the frame elements which has thehinges. The rod-shaped or belt-shaped fusible solder 62 is, as can beeasily seen in the detail illustration at the bottom right in FIG. 2,fixedly connected at its two ends in each case with the aid of afastening screw 66 to the first frame element 48 which is mounted suchthat it can move on the one hand, and to the immovable second frameelement 58 or the positionally fixed sealing and holding construction 60on the other hand and in this manner prevents in the normal case theclosure element 24 from opening. In addition, the contact pressureprevailing between the two frame elements 48, 58 can be adjusted by atensioning apparatus 70 which can be adjusted using an adjustment screw68, and therefore the tightness of the arrangement can be adjusted. Thefusible solder device can expediently contain an arrangement of aplurality of parallel fusible solders which (in the manner of a comb)are mounted with a spacing of a few millimeters and thus enable theapplication of larger closure forces during normal operation of theplant. Such a design is furthermore particularly suitable to accommodatecatalytic elements in the gap region between the individual fusiblesolder strips.

The melting point of the fusible solder 62 is selected such that theclosure element 24 is released as soon as the room temperature at thesite of the fusible solder 62 exceeds a specifically predeterminedtrigger value which is matched to the overflow opening. Therefore thefusible solder 62 is separated in its middle region between the twofixedly clamped or screwed-in ends by the starting melting process,whereupon the closure element 24 flaps downward to open as a result ofits inherent weight and due to its “suspended” installation and releasesthe overflow opening 22 for through-flow purposes. After it has beentriggered, the original state can easily be restored again by insertinga new fusible solder 62. Additionally, the exchange of the fusiblesolder device 62 can be used to easily carry out a repeating functionalexamination of the elements, and the trigger temperature can be changedand, for example, be matched to altered operational conditions of thenuclear engineering plant 4 or to altered safety regulations etc.

Alternatively to the temperature-dependent unlocking and opening of theclosure element 24, the overflow cross section can also be opened bybursting of the bursting film 50 when the bursting pressure is reached.

FIG. 3 shows a combination of two closure apparatuses 26 which arearranged directly next to one another in the overflow ceiling 36, ofwhich the left one corresponds to the closure apparatus 26 known fromFIG. 2 in terms of its configuration and its function, but the right oneis configured somewhat simpler than a purely pressure-sensitive closureapparatus 26 with a bursting film 50 clamped in at a fixed frame 72. Ingeneral it is sufficient for many areas of use and applications toprovide diversified trigger and opening mechanisms for only some of theclosure apparatuses 26, as a result of which the overall complexity forconception, manufacture and maintenance of the nuclear engineering plant4 can be kept comparatively low.

FIG. 4 illustrates an alternative embodiment of the closure apparatus 26which is particularly suitable for use in the region of lower incidentand accident temperatures, e.g. for vertical installation in a side wall74 or in a section of the intermediate wall 16. Similarly to the closureapparatus 26 known from FIG. 3, this variant contains the bursting film50 fixed to the frame element 48. The frame element 48 is mounted by anumber of hinges 56 (which are not shown here) at its bottomlongitudinal side 76 such that it can rotate on a frame-type supportingconstruction 78 which is inserted into the steel concrete wall such thatit can flap downward to open into the opening position shown herelargely due to its inherent weight when the locking is released. Theprocess of opening is assisted, in particular in its initial phase, bythe two telescope spring elements 80 which are arranged laterally andare fastened in each case at the ends of the movable frame element 48and on the wall 74 in an articulated manner.

In the normal case, the frame element 48 is kept closed by a lockingelement 83 which is mounted on that side of the supporting and holdingconstruction 78 which lies opposite the hinges 56 and in the processengages in a corresponding fitting part 82 of the frame element 48. Inthe present case, this is a pneumatic locking element 83 which unlockswhen pressurized air is applied to it. The locking element 83 isadditionally coupled via a pipeline 84, which is during normal operationof the nuclear engineering plant 4 without pressure, to atemperature-dependent trigger apparatus 86 which, in the trigger event,makes available the operating pressure which is necessary to unlock thelocking element 83. The trigger apparatus 86 can be arranged relative tothe locking element 83 expediently in a region of relatively highincident temperatures and can be conceived, depending on the length ofthe pipeline 84, also as a remote-controlled apparatus.

The trigger apparatus 86, which is illustrated in FIG. 5 before and inFIG. 4 after the trigger process, contains a pressurized-gas-filledpressurized-gas vessel 88 which can be closed on the outlet side by astop valve 90. In the normal case, i.e. before the trigger condition isreached, a spring-loaded valve tappet 92 of the stop valve 90 is held inthe closed state by a glass fuse 94. The fuse 94 can be in the form of aglass jacket, for example, and additionally contains a glass jacket 100which is arranged outside the valve housing 96 and is fixed in positionby a stop 98, to which glass jacket 100 an actuation rod 102 whichpresses against the valve tappet 92 and in the process fixes it in theclosure position is attached. The glass jacket 100 is made of a glassmaterial which, when it reaches a predetermined trigger temperature,typically 65° C. to 90° C., melts or breaks such that the previouslyblocked valve tappet 92 is made accessible. As a consequence of thepositive pressure in the pressurized-gas vessel 88, and also assisted bythe spring force of the compression spring 104, the valve tappet 92opens so that the gas located in the pressurized-gas vessel 88 canescape there from and can flow first into an intermediate space 108surrounded by a housing 106 and then into the pipeline 84 which isconnected to the pneumatic locking element 83, as a result of which thelocking element 83 is unlocked and the closure element 24 arranged inthe wall 74 opens.

In the present embodiment, the glass jacket 100 is located outside theintermediate space 108, wherein the actuation rod 102 is guided througha corresponding cutout 110 in the housing wall. The actuation rod 102can be displaced in the cutout 110 in its longitudinal direction. Thegap between the actuation rod 102 and the housing 106 is kept small andis sealed off with the aid of a sealing ring or the like (notillustrated further here), which is fixed on the edge of the cutout 110,such that no leak-related loss of pressure occurs here.

The previously mentioned function of remote triggering can also beachieved by hydraulic devices or cable pull systems.

FIG. 6 finally shows again the closure apparatus 26 known from FIG. 4,but here after a pressure-related trigger event which has led to tearingor bursting of the bursting film 50 with the frame element 48 keptclosed. The arrows 112 indicate the starting flow.

The invention claimed is:
 1. A nuclear engineering plant, comprising: acontainment including an interior and a gas-tight intermediate walldividing said interior into a plant space having a reactor pressurevessel and a primary cooling circuit and into an operating space beingwalkable during normal operation; said gas-tight intermediate wallhaving a plurality of overflow openings formed therein, said containmentfurther having closure apparatuses with closure elements each closing arespective one of said overflow openings, said closure elements openingautomatically when a trigger condition associated with said respectiveoverflow opening has been reached; a first group of said closureapparatuses opening automatically in dependence on a pressure levelindication; and a second group of said closure apparatuses openingautomatically independent of the pressure level indication; at least twoclosure apparatuses of said second group of closure apparatuses openingin dependence on a temperature level indication; each of said at leasttwo temperature level indication-dependent closure apparatuses openingas soon as an atmosphere temperature at a measurement location in saidplant space exceeds a predetermined trigger temperature selected forthat respective temperature level indication-dependent closureapparatus; said at least two temperature level indication-dependentclosure apparatuses being located at different elevations in thecontainment; and said at least two temperature-dependent closureapparatuses being configured such that one of said at least twotemperature level indication-dependent closure apparatuses located at alower elevation opens at a lower predetermined trigger temperature thananother one of said at least two temperature level indication-dependentclosure apparatuses located at a higher elevation.
 2. The nuclearengineering plant according to claim 1, wherein said containment has aplurality of trigger apparatuses based on differing operating principlesand are combined in said closure apparatuses.
 3. The nuclear engineeringplant according to claim 1, wherein at least one of said closureapparatuses opens automatically as soon as an atmosphere pressure insaid plant space exceeds a predetermined trigger pressure.
 4. Thenuclear engineering plant according to claim 1, wherein at least one ofsaid closure apparatuses opens automatically as soon as a pressuredifference between said plant space and said operating space exceeds apredetermined trigger value.
 5. The nuclear engineering plant accordingto claim 4, wherein the predetermined trigger value is in a range ofapproximately 20 mbar to 300 mbar.
 6. The nuclear engineering plantaccording to claim 1, wherein: said containment has a temperature levelindication-dependent trigger apparatus and a remote-controlledapparatus; said plant space has a ceiling; and one of said closureelements is coupled, via said remote-controlled apparatus, to saidtemperature level indication-dependent trigger apparatus which ispositioned in the higher regions of said plant space.
 7. The nuclearengineering plant according to claim 1, wherein the predeterminedtrigger temperature of said one closure apparatus is in a range ofapproximately 65° C. to approximately 90° C.
 8. The nuclear engineeringplant according to claim 1, wherein at least one of said second group ofclosure apparatuses opens automatically as soon as a concentration of agas which is one of flammable and capable of exploding and is present inan atmosphere of said plant space, exceeds a predetermined triggerconcentration.
 9. The nuclear engineering plant according to claim 8,wherein the predetermined trigger concentration is approximately 1 to 2percent by volume.
 10. The nuclear engineering plant according to claim1, wherein at least one of said closure apparatuses open in dependenceon a temperature level indication; the nuclear engineering plantadditionally including at least one element that releases heat in apresence of explosive or ignitable gases; said at least one elementbeing disposed such that heat released thereby triggers an opening ofsaid at least one of said closure apparatuses when a threshold value isexceeded.
 11. The nuclear engineering plant according to claim 1,wherein said plant space has a floor; and a first subset of saidoverflow openings, which are in each case provided with one of saidclosure apparatuses, is disposed near said floor of said plant space,and a second subset of said overflow openings is disposed in higherregions, and a difference in height is more than 5 meters between saidfirst and second subsets.
 12. The nuclear engineering plant according toclaim 11, wherein said containment has a number of recombiners mountedon an inside wall of said plant space between said first subset and saidsecond subset of said overflow openings.
 13. The nuclear engineeringplant according to claim 1, wherein an area covered overall by saidclosure elements is approximately 0.1 to 0.5 times a horizontalcross-sectional area of said plant space.
 14. The nuclear engineeringplant according to claim 1, wherein said containment has an additionalscreen disposed in a flow opening region of said plant space, and aninflow cross section of said flow opening region being delimited by saidadditional screen is at least twice an inflow cross section ofassociated ones of said overflow openings.
 15. The nuclear engineeringplant according to claim 1, wherein said containment has a planarholding and sealing construction formed from steel, said closureelements are fitted over a large area in said planar holding and sealingconstruction.
 16. The nuclear engineering plant according to claim 1,wherein said containment has a cooling apparatus for cooling air in saidplant space and has a cooling power such that a room temperature in saidplant space can be reduced during normal operation permanently to lessthan 60° C.
 17. The nuclear engineering plant according to claim 1,wherein said containment has a suction apparatus for air which is insaid plant space and a purifying apparatus for purifying anddecontaminating sucked-off air.
 18. The nuclear engineering plantaccording to claim 11, wherein: said second subset of said overflowopenings is disposed in sections of said gas-tight intermediate wallwhich forms a ceiling of said plant space; and said difference in heightis more than 20 meters.
 19. The nuclear engineering plant according toclaim 8, wherein the concentration of the gas is a concentration ofhydrogen.
 20. The nuclear engineering plant according to claim 10,wherein the element is a catalytic element.